ML022620712

From kanterella
Revision as of 13:59, 25 March 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search

Facsimile Transmission, Issues to Be Discussed in an Upcoming Conference Call
ML022620712
Person / Time
Site: Millstone Dominion icon.png
Issue date: 09/23/2002
From: Richard Ennis
NRC/NRR/DLPM/LPD1
To: Andersen J
NRC/NRR/DLPM/LPD1
Ennis R, NRR/DLPM, 415-1420
References
TAC MB5799
Download: ML022620712 (3)


Text

September 23, 2002 MEMORANDUM TO: James W. Andersen, Acting Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Sr. Project Manager, Section 2 /RA/

Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation

SUBJECT:

MILLSTONE POWER STATION, UNIT NO. 2, FACSIMILE TRANSMISSION, ISSUES TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MB5799)

The attached information was transmitted by facsimile on September 19, 2002, to Mr. Ravi Joshi of Dominion Nuclear Connecticut, Inc. (the licensee). This information was transmitted to facilitate a upcoming conference call in order to clarify the licensees amendment request dated August 1, 2002. The proposed amendment would revise TS 3.7.1.1, Plant Systems: Turbine Cycle Safety Valves, to reflect results of a reanalysis of overpressurization events to reinstate the capability to operate, at corresponding reduced power levels, with up to four main steam line code safety valves in each main steam line inoperable. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.

Docket No. 50-336

Attachment:

Issues for Discussion in Upcoming Telephone Conference

September 23, 2002 MEMORANDUM TO: James W. Andersen, Acting Chief, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation FROM: Richard B. Ennis, Sr. Project Manager, Section 2 /RA/

Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation

SUBJECT:

MILLSTONE POWER STATION, UNIT NO. 2, FACSIMILE TRANSMISSION, ISSUES TO BE DISCUSSED IN AN UPCOMING CONFERENCE CALL (TAC NO. MB5799)

The attached information was transmitted by facsimile on September 19, 2002, to Mr.

Ravi Joshi of Dominion Nuclear Connecticut, Inc. (the licensee). This information was transmitted to facilitate a upcoming conference call in order to clarify the licensees amendment request dated August 1, 2002. The proposed amendment would revise TS 3.7.1.1, Plant Systems: Turbine Cycle Safety Valves, to reflect results of a reanalysis of overpressurization events to reinstate the capability to operate, at corresponding reduced power levels, with up to four main steam line code safety valves in each main steam line inoperable. This memorandum and the attachment do not convey a formal request for information or represent an NRC staff position.

Docket No. 50-336

Attachment:

Issues for Discussion in Upcoming Telephone Conference DISTRIBUTION PUBLIC JAndersen REnnis KDesai PDI-2 Reading ACCESSION NO.: ML022620712 OFFICE PDI-2/PM NAME REnnis DATE 09/20/2002 OFFICIAL RECORD COPY ISSUES FOR DISCUSSION IN UPCOMING TELEPHONE CONFERENCE

REGARDING PROPOSED AMENDMENT TO TECHNICAL SPECIFICATIONS OPERATION WITH MAIN STEAM LINE CODE SAFETY VALVES INOPERABLE MILLSTONE POWER STATION, UNIT NO. 2 DOCKET NO 50-336 By letter dated August 1, 2002, Dominion Nuclear Connecticut, Inc. (the licensee) submitted a proposed amendment to the Technical Specifications (TSs) for Millstone Power Station, Unit No. 2 (MP2). The proposed amendment would revise TS 3.7.1.1, Plant Systems: Turbine Cycle Safety Valves, to reflect results of a reanalysis of overpressurization events to reinstate the capability to operate, at corresponding reduced power levels, with up to four main steam line code safety valves (MSSVs) in each main steam line inoperable.

The Nuclear Regulatory Commission (NRC) staff has reviewed the information the licensee provided that supports the proposed TS changes and would like to discuss the following issues to clarify the submittal dated August 1, 2002:

1) Was the reanalysis performed using computer codes and methods that were approved by the NRC staff?
2) Which computer code(s) and methodology was used for the reanalysis?
3) Discuss your method of analysis to determine the maximum power levels and corresponding high trip setpoints for the values shown in proposed TS Table 3.7.1.

Attachment